ML20134K884
| ML20134K884 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 08/26/1985 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20134K888 | List: |
| References | |
| NUDOCS 8508300492 | |
| Download: ML20134K884 (10) | |
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j WASHINGTON, D. C. 20555 SOUTH. CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUM 4ER NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 44 License No. NPF-12 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment to the Virgil C. Summer Nuclear Station, Unit No. 1 (the facility) Facility Operating License No. NPF-12 filed by the South Carolina Electric & Gas Company acting for itself and South Carolina Public Service Authority (the licensees), dated April 9, 1985, and supplemented May 20, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this license amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment and paragraph 2.C(2) of Facility Operating License No. NPF-12 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 44, are hereby incorporated into this license.
South Carolina Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8509300492 850826 PDR ADOCK 05000395 P
t 2-3.
This license amendment is effective seven days after its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor 3. Adensam, Chief licensing Branch No. 4 Division of licensing
Enclosure:
Technical Specification Changes Date of Issuance:
August 26, 1985 O
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ATTACHMENT TO LICENSE AMENDMENT NO. 44 FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
The corresponding 4
overleaf pages are also provided to maintain document completeness.
Amended Overleaf Page Page VI V
XIII XIV 3/4 5-9 83/4 5-2 B3/4 6-1 Pages 3/4 5-10 and 3/4 5-11 are deleted.
Page B3/4 5-3 is deleted.
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation..............................
3/4 4-1 Hot Standby..............................................
3/4 4-2 Hot Shutdown.............................................
3/4 4-3 Cold Shutdown Loops Ft11ed.............................
3/4 4-5 Cold Shutdown - Loops Not Ft11ed....................'.....
3/4 4-6 3/4.4.2 SAFETY VALVES SHUTD0WN...............................................
3/4 4-7 0PERATING..............................................
3/4 4-8 3/4.4.3 PRESSURIZER..............................................
3/4 4-9 3/4.4.4 RELIEF VALVES............................................
3/4 4-10 3/4.4.5 STEAM GENERATORS.........................................
3/4 4-11 3/4.4.6 REACTOR COOLANT SYSTEM' LEAKAGE Leakage Detection Systems................................
3/4 4-18 Operational Leakage......................................
3/4 4-19 3/4.4.7 CHEMISTRY................................................
3/4 4-22 3/4.4.8 SPECIFIC ACTIVITY........................................
3/4 4-25 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System...................................
3/4 4-29 Pressurizer..............................................
3/4 4-33 Overpressure Protection Systems..........................
3/4 4-34 3/4.4.10 STRUCTU RA L INTEGRITY....................................
3/4 4-36 s
SUMMER-UNIT 1 V
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATORS.............................................
3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T,yg >
350*F...........................
3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - T,yg <
350*F...........................
3/4 5-7 3/4.5.4 REFUELING WATER STORAGE TANK.............................
3/4 5-9 SulWER-UNIT 1 VI Amendment No. 44 1c ; '
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INDEX BASES SECTION PAGE 3/4.4.6 STEAM GENERATORS..........................................
B 3/4 4-3 3/4.4.7 REACTOR COOLANT SYSTEM LEAKAGE............................
B 3/4 4-4 i
3/4.4.8 CHEMISTRY.................................................
B 3/4 4-5
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t 3/4.4.9 SPECIFIC ACTIVITY.........................................
B 3/4 4-5 3/4.4.10 PRESSURE / TEMPERATURE LIMITS...............................
B 3/4 4-6 3/4.4.11 STRUCTURAL INTEGRITY......................................
B 3/4 4-15 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATORS..............................................
B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS...............................
B 3/4 5-1 3/4.5.4 REFUELING WATER STORAGE TANK (RWST).......................
B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT.......................................
B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS......................
B 3/4 6-3 3/4.6.3 PARTICULATE IODINE CLEANUP SYSTEM.........................
B 3/4 6-4 3/4.6.4 CONTAINMENT ISOLATION VALVES..............................
B 3/4 6-5' 3/4.6.5 COMBUSTIBLE GAS CONTR0L...................................
B 3/4 6-5 l
t SUPMER-UNIT 1 XIII Amendment No. 44 t
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a-0 INDEX BASES
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SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE.............................................
B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...........
B 3/4 7-3 3/4.7.3 COMPONENT COOLING WATER SYSTEM...........................
B 3/4 7-3 3/4.7.4 SERVICE WATER SYSTEM......................................
B 3/4 7-3 3/4.7.5 ULTIMATE HEAT SINK........................................
B 3/4 7-3 3/4.7.6 CONTROL ROOM NORMAL AND EMERGENCY AIR HANDLING SYSTEM............................
B 3/4 7-4 3/4.7.7 SHUBBERS..................................................
B 3/4 7-4 3/4. 7. 8 S EALED SOURCE CONTAMINATION................................
B 3/4 7-6 i
3/4.7.9 rIRE SUPPRESSION SYSTEMS...................................
B 3/4 7-6 3/4.7.10 rIRe RATEo ASSEMBtIES.....................................
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B 3/4 7-7 3/4.7.11 AREA TEMPERATURE MONITORING...............................
B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2 and 3/4.8.3 A.C. SOURCES, D.C SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS.......................
B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIONDEVICES...................
B 3/4 8-3
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SUMMER-UNIT 1 XIV 4
EMERGENCY CORE COOLING SYSTEMS 3/4.5.4 REFUELING WATER STORAGE TANK LIMITING CONDITION FOR OPERATION 3.5.5 The refueling water storage tank (RWST) shall be OPERABLE with:
a.
A minimum contained borated water volume of 453,800 gallons, b.
A boron concentration of between 2000 and 2100 ppm of boron, and c.
A minimum water temperature of 40*F.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With the refueling water storage tank inoperable, restore the tank to CPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.5.5 The RWST shall be demonstrated OPERABLE:
a.
At least once per 7 days by:
1.
Verifying the contained borated water volume in the tank, and 2.
Verifying the boron concentration of the water.
b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when the outside air temperature is less than 40*F.
SUMMER - UNIT 1 3/4 5-9 Amendment No. 44 l
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3/4.5 EMERGENCY CORE COOLING SYSTEMS I
BASES 3/4.5.1 ACCUMULATORS The OPERABILITY of each Reactor Coolant System (RCS) accumulator ensures that a sufficient volume of borated water will be immediately forced into the reactor core through each of the cold legs in the event the RCS pressure falls below the iressure of the accumul.ators. This initial surge of water into the core provides
- he initial cooling mechanism during large RCS pipe ruptures.
The limits on accumulator volume, boron concentration and pressure ensure that the assumptions used for accumulator injection in the safety analysis are met.
The accumulator power operated isolation valves are considered to be
" operating bypasses" in the context of IEEE Std. 279-1971, which requires that bypasses of a protective functior be removed automatically whenever permissive conditions are not met.
In addition, as these accumulator isolation valves fail to meet single failure criteria, removal of power to the valves is required.
- l The limits for operation with an accumulator inoperable for any reason cxcept an isolation valve closed minimizes the time exposure of the plant to a LOCA event occurring concurrent with failure of an additional accumulator which may result in unacceptabl(~ peak cladding temperatures.
If a closed isolation valve cannot be immediately opened, the full capability of one accumulator is not available and prompt action is required to place the reactor in a mode where this capability is not required.
i 3/4.5.2 and 3/4.5.3 EMERGENCY CORE COOLING SYSTEM (ECCS) SUBSYSTEMS l
The OPERABILITY of two independent ECCS subsystems ensures that sufficient emergency core cooling capability will be available in the event of a LOCA assuming the loss of one subsystem through any single failure consideration.
Either subsystem operating in conjunction with the accumulators is capable of supplying sufficient core cooling to limit the peak cladding temperatures within acceptable limits for all postulated break sizes ranging from the double ended break of the largest RCS cold leg pipe downward.
In addition, cach ECCS subsystem provides long term core cooling capability in the recirculation mode during the accident recovery period.
With the RCS temperature below 350*F, one OPERABLE ECCS subsystem is acceptable without single failure consideration on the basis of the stable i
j reactivity condition of the reactor and the limited core cooling requirements.
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SUtWER - UNIT 1 8 3/4 5-1
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i EMERGENCY CORE COOLING SYSTEMS BASES ECCS SUBSYSTEMS (Continued)
The limitation for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps except the required OPERABLE charging pump to be inoperable below 300*F provides assurance that a mass addition pressure transient can be relieved by the i
operation of a single PORV.
The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the safety analyses tre met and that subsystem OPERABILITY is maintained.
Surveillance requirements for throttle valve position stops and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA.
Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to:
(1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration, (2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses.
3/4.5.4 REFUELING WATER STORAGE TANK The OPERABILITY of the Refueling Water Storage Tank (RWST) as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA.
The limits on RWST minimum volume and boron concentration ensure that 1) sufficient water is available within contain-ment to permit recirculation cooling flow to the core, and 2) the reactor will remain subcritical in the cold condition following mixing of the RWST and the j
RCS water volumes with all control rods inserted except for the most reactive control assembly.
These assumptions are consistent with the LOCA analyses.
Additionally, the OPERABILITY of the Refueling Water Storage Tank as part of the ECCS ensures that sufficient negative reactivity is injected into the core to counteract any positive increase in reactivity caused by RCS system cooldown.
RCS cooldown can be caused by inadvertent depressuriza-l tion, a loss-of-coolant accident, or a steam line rupture.
4 The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.
The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 8.5 and 11.0 for the solution recirculated within containment after a LOCA.
This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on Eechanical systems and components.
i SUMER - UNIT 1 B 3/4 5-2 Amendment No. 44 a
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